Fuels for sodium-cooled fast reactors: US perspective

Crawford, Douglas C.; Porter, David; Hayes, S. L.

doi:10.1016/j.jnucmat.2007.05.010

Cited by 255 publications

(92 citation statements)

References 46 publications

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“…As for the material of chamber, alumina is utilized. A wide variety of in-pile transient tests [4] and out-of-pile heating tests [2,3,5,6] in the IFR (Integral Fast Reactor) program revealed the transient performance of metal fuel. A series of tests, called the M-series, was performed at the Transient Reactor Test Facility (TREAT) in ANL (Argonne National Laboratory)-Idaho (currently INL) to study the cladding failure threshold during transient overpower (TOP) events [4].…”

Section: Methodsmentioning

confidence: 99%

Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Kim¹,

Cheon²,

Kim³

et al. 2016

Metals

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A microstructure observation using an optical microscope, SEM and EPMA was performed for the irradiated U-10Zr and U-10Zr-5Ce fuel slugs with a T92 cladding specimen after a high-temperature heating test. Also, the measured eutectic penetration rate was compared with the value predicted by the existing eutectic penetration correlation being used for design and modeling purposes. The heating temperature and duration time for the U-10Zr/T92 specimen were 750 • C and 1 h, and those for the U-10Zr-5Ce/T92 specimen were 800 • C and 1 h. In the case of the U-10Zr/T92 specimen, the migration phenomena of U, Zr, Fe, and Cr as well as the Nd lanthanide fission product were observed at the eutectic melting region. The measured penetration rate was similar to the value predicted by the existing eutectic penetration rate correlation. In addition, when comparing with measured eutectic penetration rates for the unirradiated U-10Zr fuel slug with FMS (ferritic martensitic steel, HT9 or Gr.91) cladding specimens which had been reported in the literature, the measured eutectic penetration rate for the irradiated fuel specimen was higher than that for the unirradiated U-10Zr specimen. In the case of the U-10Zr-5Ce/T92 specimen in which there had been a gap between the fuel slug and cladding after the irradiation test, the eutectic melting region was not found because contact between the fuel slug and cladding did not take place during the heating test.

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Section: Methodsmentioning

confidence: 99%

Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Kim¹,

Cheon²,

Kim³

et al. 2016

Metals

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“…[21]. Moreover it is important to underpin that the development of advanced fuels like MOX, i.e., modelling process, their transient behaviour due to power excursion, and the proliferation resistance (for both thermal and fast reactors) require dedicated R&D. The molecular dynamics calculations used to simulate the elastic properties and thermal expansivity for a range of mixed oxide compositions of UO 2 blended with other actinide oxides (for example: ThO 2 , PuO 2 or Pu-AmO 2 ) can be found in [27][28][29]. For many innovative nuclear fuel applications, the understanding of oxygen self-diffusion in a fuel over a range of temperatures is still an important issue [30].…”

Section: Short Description Of Nea/oecd Study On Performance Comparisomentioning

confidence: 99%

Comparison and Screening of Nuclear Fuel Cycle Options in View of Sustainable Performance and Waste Management

Schwenk-Ferrero

Андрианов

2017

Sustainability

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Abstract:Is it true that a nuclear technology approach to generate electric energy offers a clean, safe, reliable and affordable, i.e., sustainable option? In principle yes, however a technology impact on the environment strongly depends on the actual implementation bearing residual risks due to technical failures, human factors, or natural catastrophes. A full response is thus difficult and can be given first when the wicked multi-disciplinary issues get well formulated and "resolved". These problems are lying at the interface between: the necessary R&D effort, the industrial deployment and the technology impact in view of the environmental sustainability including the management of produced hazardous waste. As such, this problem is clearly of multi-dimensional nature. This enormous complexity indicates that just a description of the problem might cause a dilemma. The paper proposes a novel holistic approach applying Multi-Criteria Decision Analysis to assess the potential of nuclear energy systems with respect to a sustainable performance. It shows how to establish a multi-level criteria structure tree and examines the trading-off techniques for scoring and ranking of options. The presented framework allows multi-criteria and multi-group treatment. The methodology can be applied to support any pre-decisional process launched in a country to find the best nuclear and/or non-nuclear option according to national preferences and priorities. The approach addresses major aspects of the environmental footprint of nuclear energy systems. As a case study, advanced nuclear fuel cycles are analyzed, which were previously investigated by the Nuclear Energy Agency (NEA/OECD) expert group WASTEMAN. Sustainability facets of waste management, resource utilization and economics are in focus.Keywords: advanced nuclear fuel cycles; waste management; resource utilisation; economics; performance comparison, multi-criteria decision analysis; sensitivity/uncertainty analysis, environmental footprint BackgroundInnovative electrical energy generating technologies should be sustainable, i.e., clean, safe, reliable and affordable and moreover able to preserve resources and minimise liabilities [1]. The nuclear technology option might compete in this sense with other large-scale energy producing technologies as, for instance those consuming coal or oil resources [2]. However, very much like other non-nuclear energy generation options, a nuclear option produces hazardous radioactive waste (radwaste)-called high-level waste (HLW) that contains long-living radionuclides. Therefore HLW should be isolated from the biosphere by a disposal site/system and an enclosure in special facilities, called HLW repositories [3]. This is the reason why nuclear waste management is of public concern in some

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“…The cladding chosen for this analysis was HT-9, a typical high temperature steel cladding with relatively high percentages of chromium detailed by Klueh and Harries (2001), Crawford, et al (2007), and Walters, et al (2011). This cladding material has been tested in several sodium fast experimental reactors, including the Experimental Breeder Reactor I and II (EBR-I and EBR-II) and the Fast Flux Test Facility (FFTF), where its commercial viability was proven when exposed to a sodium environment.…”

Section: K Eff Geometrymentioning

confidence: 99%

Burnup concept for a long-life fast reactor core using MCNPX.

Holschuh¹,

Lewis²,

Parma³

2013

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This report describes a reactor design with a burnup concept for a long-life fast reactor core that was evaluated using Monte Carlo N-Particle eXtended (MCNPX). The current trend in advanced reactor design is the concept of a small modular reactor (SMR). However, very few of the SMR designs attempt to substantially increase the lifetime of a reactor core, especially without zone loading, fuel reshuffling, or other artificial mechanisms in the core that "flatten" the power profile, including non-uniform cooling, non-uniform moderation, or strategic poison placement. Historically, the limitations of computing capabilities have prevented acceptable margins in the temporal component of the spatial excess reactivity in a reactor design, due primarily to the error in burnup calculations.This research was performed as an initial scoping analysis into the concept of a long-life fast reactor. It can be shown that a long-life fast reactor concept can be modeled using MCNPX to predict burnup and neutronics behavior. The inherent characteristic of this conceptual design is to minimize the change in reactivity over the lifetime of the reactor. This allows the reactor to operate substantially longer at full power than traditional Light Water Reactors (LWRs) or other SMR designs.For the purpose of this study, a single core design was investigated: a relatively small reactor core, yielding a medium amount of power (~200 to 400 MW th ). The results of this scoping analysis were successful in providing a preliminary reactor design involving metal U-235/U-238 fuel with HT-9 fuel cladding and sodium coolant at a 20% volume fraction.

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Fuels for sodium-cooled fast reactors: US perspective

Cited by 255 publications

References 46 publications

Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Comparison and Screening of Nuclear Fuel Cycle Options in View of Sustainable Performance and Waste Management

Burnup concept for a long-life fast reactor core using MCNPX.

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